Abstract
A semi-automated instrumental gamma-spectrometric measuring system with a sample changer has been developed for determination of the radioactive fission products coming from different parts of the primary coolant circuit. The measuring geometry assures higher sensitivities under normal operation conditions and lower ones for significant fuel cladding failures. The minimal detection limits are in the range of some ten Bq/l.
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References
Detection and Location of Failed Fuel Elements, IAEA Report of a Panel, Vienna, 1968.
K. H. NEEB, BMFT-Forschungsbericht K-73-11, 1973.
G. BUDNICK, K. H. NEEB, Atom und Strom, (1974) No. 3-4.
K. H. NEEB, S. HILLER: VGB Kraftwerstechnik 54 Heft 12, Dez. 1974.
H. S. KUHLMANN, R. I. CORNWELL, A. J. GOLDBERT: IEEE Trans. Nucl. Sci., 25 (1978) No. 1.
BÓDIZS D., DÉSI S., KEÖMLEY G., BOGÁNCS J.: Energia és Atomtechnika 35 (1982) 248 (in Hungarian).
L. A. CURRIE: Anal. Chem., 40 (1968) 583.
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Bódizs, D., Dési, S., Keömley, G. et al. Determination of radioactivity concentrations of fission products in the primary coolant of nuclear power plants. Journal of Radioanalytical and Nuclear Chemistry, Articles 147, 347–353 (1991). https://doi.org/10.1007/BF02040383
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DOI: https://doi.org/10.1007/BF02040383